Ringhals Unit 3 and 4—Fluence Determination in a Historic and Future Perspective

E. Green, J. Roudén, P. Efsing
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引用次数: 1

Abstract

The Ringhals site is situated on the Swedish southwest coastline. At the site, there are four operating nuclear power plants. Historically, the Swedish policy has been that the nuclear power plants were to be closed in 2010. The present position is to operate the units until their technical and economic lifetime has run out. The units shall be maintained and invested in to ensure a lifetime of at least 50 years, but the actions taken shall not limit the time to this date. When the initial surveillance capsules were evaluated, it was noted that the material properties of the weld material of unit 3 and 4 showed some deviations from the expected behaviour. Currently there is an extensive project running for re-evaluating the embrittlement situation from a long-term operating perspective. One part of the project is aimed at more accurately determining the fluence levels of the reactor pressure vessels (RPVs). The basis for the early evaluations of the dosimeters in the surveillance capsules and the corresponding fluence evaluation had an operating lifetime of 25 years as a target value. Therefore, the accuracy and refinement of the measurement and calculation were taken to be good enough to suit this life span. Looking back at the results from the dosimetry measurements there are a few discrepancies. Some of the dosimeters were disintegrated and some measurements had comparatively large uncertainties. When starting this project there were some re-evaluations done with the old fluence prediction model. For every new run and refinement there appeared new difficulties, and the decision was to start the evaluation from scratch. Then there are two questions remaining regarding the fluence: What is the current fluence level? What will the resulting fluence be after 60 years of operation, when we have up-rated output power of both reactors? This paper aims to describe the view of the fluence evaluation in the surveillance program of the RPV, both in a historical and prospective view.
环室第3单元和第4单元:历史和未来视角下的通量测定
Ringhals遗址位于瑞典西南海岸线。在这个地方,有四座正在运行的核电站。从历史上看,瑞典的政策是在2010年关闭核电站。目前的立场是把机组运行到技术经济寿命结束为止。对机组的维护和投资应当保证至少50年的使用寿命,但采取的措施不应限于此日期。当最初的监测胶囊被评估时,注意到3号和4号单元的焊接材料的材料性能与预期的行为有一些偏差。目前有一个广泛的项目正在运行,从长期操作的角度重新评估脆化情况。该项目的一部分目的是更准确地确定反应堆压力容器(RPVs)的影响水平。监测胶囊内剂量计的早期评价和相应的影响评价的基础是以25年的使用寿命为目标值。因此,测量和计算的精度和精细化被认为足以适应这个寿命。回顾剂量测量的结果,有一些差异。有些剂量计已解体,有些测量结果有较大的不确定度。在开始这个项目时,对旧的影响预测模型进行了一些重新评估。对于每一次新的运行和改进,都会出现新的困难,于是决定从头开始评估。那么关于影响力还有两个问题:当前的影响力水平是多少?当两个反应堆的输出功率都提高后,运行60年后的结果会是什么?本文旨在从历史和未来两方面阐述对RPV监测项目影响评估的看法。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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